Nuclear power source starting system and method and nuclear reactor

Abstract

The invention provides a nuclear power source starting system and method and a nuclear reactor, the nuclear power source starting system is suitable for starting the nuclear reactor, the nuclear reactor comprises a reactor core, the reactor core comprises a rotary drum and a base body, the nuclear power source starting system comprises a measuring unit, and the measuring unit comprises a plurality of out-of-reactor detectors, the out-of-reactor detector is used for detecting a plurality of reactor core signals of the nuclear reactor; the intelligent monitoring unit is used for receiving and analyzing the plurality of reactor core signals and acquiring a plurality of reactor core parameters of the reactor core according to the reactor core signals; the intelligent monitoring unit sends a control instruction for controlling the rotary drum to the control unit according to the multiple reactor core parameters, and the control unit controls the rotating angle and the rotating speed of the rotary drum according to the control instruction. According to the nuclear power source starting system and method and the nuclear reactor provided by the invention, the drum can be controlled according to the real-time state of the reactor, so that the reactor starting process is automatically adjusted and optimized, and the reactor starting safety of the nuclear reactor is further ensured.

Description

Technical Field

[0001] The present application mainly relates to the field of nuclear power technology, and in particular to a nuclear power supply startup system and method and a nuclear reactor. Background Art

[0002] As a typical type of micro-mobile nuclear power source, heat pipe cooled reactor (heat pipe reactor) has the advantages of excellent inherent safety, long operation cycle, high power density, compact core structure, convenient transportation, etc. It is an important development direction for future nuclear energy and even energy development. However, the startup process of heat pipe reactor is a rapid power doubling, so it is the most unstable stage of the heat pipe section.

[0003] During the startup process, the introduction and control of core reactivity is a key factor in the startup process of nuclear reactors. For heat pipe reactors, the rotation angle and speed of the control drum are usually set in advance at different stages of the startup process to introduce reactivity into the core. This method cannot automatically adjust and optimize the rotation angle and speed of the control drum online according to the real-time status of the reactor. The startup steps are relatively cumbersome and require manual operation, which can easily lead to extended startup time and human errors in heat pipe reactors. Summary of the invention

[0004] The technical problem to be solved by the present application is to provide a nuclear power startup system and method and a nuclear reactor, which can control the drum according to the real-time status of the reactor to achieve automatic adjustment and optimization of the startup process, and further ensure the startup safety of the nuclear reactor.

[0005] To solve the above technical problems, the present application provides a nuclear power starting system, which is suitable for starting a nuclear reactor, wherein the nuclear reactor includes a core, wherein the core includes a drum and a matrix, and the nuclear power starting system includes: a measuring unit, wherein the measuring unit includes a plurality of off-core detectors, and the off-core detectors are used to detect a plurality of core signals of the nuclear reactor; an intelligent monitoring unit, wherein the intelligent monitoring unit receives and analyzes the plurality of core signals, and obtains a plurality of core parameters of the core according to the core signals; and a control unit, wherein the intelligent monitoring unit sends a control instruction for controlling the drum to the control unit according to the plurality of core parameters, and the control unit controls the rotation angle and rotation speed of the drum according to the control instruction.

[0006] Optionally, the plurality of core parameters include real-time reactivity, power level, power distribution, temperature distribution, core matrix stress distribution and / or core matrix geometric deformation of the nuclear reactor.

[0007] Optionally, the intelligent monitoring unit comprises a digital reactivity calculator, which is suitable for obtaining the real-time reactivity of the core according to the core signal.

[0008] Optionally, the digital reactivity calculator calculates the effective multiplication factor (k eff ) to obtain the real-time reactivity of the core, where the effective multiplication factor (k eff ) is obtained by the following formula:

[0009]

[0010] Optionally, the intelligent monitoring unit also includes a power level measuring instrument and a power distribution measuring instrument, wherein the power level measuring instrument is suitable for obtaining power changes of the nuclear reactor, and the power distribution measuring instrument is suitable for obtaining power distribution within the nuclear reactor.

[0011] Optionally, the intelligent monitoring unit performs fault analysis on the nuclear reactor based on historical core signals and real-time core signals.

[0012] In order to solve the above technical problems, the present application provides a nuclear power startup method, which is applicable to the nuclear power startup system as described above, and the nuclear power startup method comprises the following steps: detecting multiple core signals of the nuclear reactor by multiple off-core detectors of the measuring unit; receiving and analyzing the multiple core signals detected by the measuring unit by the intelligent monitoring unit, and obtaining multiple core parameters of the core according to the core signals; sending a control instruction for controlling the drum to the control unit by the intelligent monitoring unit, and the control unit controls the rotation angle and rotation speed of the drum according to the control instruction.

[0013] Optionally, sending a control instruction for controlling the drum to the control unit through the intelligent monitoring unit comprises the following steps: the control unit controls the drum to rotate from an initial position to introduce positive reactivity, and the intelligent monitoring unit continuously calculates the effective increment factor (k eff ); Determine the effective value-added factor (k eff ) is within the first value interval, if the effective value-added factor (k eff ) is in the first numerical interval, it is determined that the core is in a critical state, and at this time, the drum is controlled to stop rotating; it is determined whether the time that the core is in the critical state is greater than a preset time, and if the determination result is yes, the drum is controlled to continue rotating; the intelligent monitoring unit continuously calculates the power level of the core, and determines whether the power level is greater than or equal to a preset power level, and if the determination result is yes, the drum is controlled to stop rotating.

[0014] Optionally, the first numerical interval is [1-β eff , 1+β eff ].

[0015] In order to solve the above technical problems, the present application provides a nuclear reactor, including a core, wherein the core includes a drum and a matrix, and the nuclear reactor is suitable for starting by the nuclear power starting system as described above.

[0016] Optionally, the core further includes a reactor reflector layer, a fuel and heat pipe region and a shutdown rod, the fuel and heat pipe region includes a heat pipe, and the heat pipe includes an evaporation section, an insulation section and a condensation section.

[0017] Compared with the prior art, the present invention detects multiple core signals of a nuclear reactor through a measuring unit, and processes the core signals through an intelligent monitoring unit to obtain an effective value-added factor (k eff ), core parameters, and then the control unit controls the drum according to the core parameters to achieve automatic adjustment and optimization of the start-up process according to the real-time state of the reactor. Furthermore, the present application proposes a nuclear power startup method, which can ensure that the nuclear power startup system automatically adjusts and optimizes the start-up process during the start-up process, thereby further ensuring the start-up safety of the nuclear reactor. BRIEF DESCRIPTION OF THE DRAWINGS

[0018] The accompanying drawings are included to provide a further understanding of the present application. They are included and constitute a part of the present application. The accompanying drawings illustrate embodiments of the present application and together with the present specification serve to explain the principles of the present application. In the accompanying drawings:

[0019] Figure 1 This is a schematic diagram of a structural module of a nuclear power startup system in an embodiment of the present application;

[0020] Figure 2 It is a flow chart of a nuclear power source startup method in one embodiment of the present application;

[0021] Figure 3 It is a structural schematic diagram of a nuclear reactor in one embodiment of the present application. DETAILED DESCRIPTION

[0022] In order to more clearly illustrate the technical solutions of the embodiments of the present application, the following is a brief introduction to the drawings required for the description of the embodiments. Obviously, the drawings described below are only some examples or embodiments of the present application. For ordinary technicians in this field, the present application can also be applied to other similar scenarios based on these drawings without creative work. Unless it is obvious from the language environment or otherwise explained, the same reference numerals in the figures represent the same structure or operation.

[0023] As shown in this application and claims, unless the context clearly indicates an exception, the words "a", "an", "an" and / or "the" do not refer to the singular and may also include the plural. Generally speaking, the terms "include" and "comprise" only indicate the inclusion of the steps and elements that have been clearly identified, and these steps and elements do not constitute an exclusive list. The method or device may also include other steps or elements.

[0024] Unless otherwise specifically stated, the relative arrangement, numerical expressions and numerical values ​​of the parts and steps set forth in these embodiments do not limit the scope of the present application. At the same time, it should be understood that, for ease of description, the sizes of the various parts shown in the accompanying drawings are not drawn according to the actual proportional relationship. The technology, method and equipment known to those of ordinary skill in the relevant field may not be discussed in detail, but in appropriate cases, the technology, method and equipment should be considered as a part of the authorization specification. In all examples shown and discussed here, any specific value should be interpreted as being merely exemplary, rather than as a limitation. Therefore, other examples of exemplary embodiments may have different values. It should be noted that similar reference numerals and letters represent similar items in the following drawings, so that once a certain item is defined in an accompanying drawing, it does not need to be further discussed in subsequent drawings.

[0025] In the description of the present application, it should be understood that the directions or positional relationships indicated by directional words such as "front, back, up, down, left, right", "lateral, vertical, perpendicular, horizontal" and "top, bottom" are usually based on the directions or positional relationships shown in the drawings, and are only for the convenience of describing the present application and simplifying the description. Unless otherwise specified, these directional words do not indicate or imply that the device or element referred to must have a specific direction or be constructed and operated in a specific direction, and therefore cannot be understood as limiting the scope of protection of the present application; the directional words "inside and outside" refer to the inside and outside relative to the contours of each component itself.

[0026] For ease of description, spatially relative terms such as "above", "above", "on the upper surface of", "above", etc. may be used here to describe the spatial positional relationship between a device or feature and other devices or features as shown in the figure. It should be understood that spatially relative terms are intended to include different orientations of the device in use or operation in addition to the orientation described in the figure. For example, if the device in the accompanying drawings is inverted, the device described as "above other devices or structures" or "above other devices or structures" will be positioned as "below other devices or structures" or "below other devices or structures". Thus, the exemplary term "above" can include both "above" and "below". The device can also be positioned in other different ways (rotated 90 degrees or in other orientations), and the spatially relative descriptions used here are interpreted accordingly.

[0027] In addition, it should be noted that the use of words such as "first" and "second" to define components is only for the convenience of distinguishing the corresponding components. If not otherwise stated, the above words have no special meaning and cannot be understood as limiting the scope of protection of this application. In addition, although the terms used in this application are selected from well-known and commonly used terms, some terms mentioned in the specification of this application may be selected by the applicant at his or her discretion, and their detailed meanings are explained in the relevant parts of the description of this article. In addition, it is required to understand this application not only by the actual terms used, but also by the meaning implied by each term.

[0028] This application refers to Figure 1 A nuclear power startup system 10 (hereinafter referred to as "startup system 10") is proposed, which is suitable for Figure 3 The nuclear reactor 30 shown in the figure mainly includes a core 31, wherein the core 31 includes a drum 32 and a matrix 33. Figure 1 Introducing the startup system 10.

[0029] like Figure 1 As shown, the startup system 10 mainly includes a measuring unit, an intelligent monitoring unit and a control unit. Specifically, the measuring unit includes a plurality of off-core detectors 11, which are used to detect a plurality of core signals of the nuclear reactor. For example, the off-core detectors are arranged at the outer edge of the core 31 (e.g. Figure 3 As shown), this embodiment preferably uses a high-sensitivity and high-temperature resistant out-of-pile detector.

[0030] Furthermore, the startup system 10 includes an intelligent monitoring unit, which receives and analyzes a plurality of core signals transmitted from the measuring unit to the intelligent monitoring unit, and obtains a plurality of core parameters of the core 31 according to the core signals. In this embodiment, the plurality of core parameters include real-time reactivity, power level, power distribution, temperature distribution, core matrix stress distribution and / or core matrix geometric deformation of the nuclear reactor.

[0031] In this embodiment, the intelligent monitoring unit further includes a digital reactivity calculator, which can obtain the real-time reactivity of the core according to the core signal. In this embodiment, the digital reactivity calculator preferably calculates the effective multiplication factor (k eff ) to obtain the real-time reactivity of the core. The core signal obtained by the measuring unit can be processed quickly and accurately by using a digital reactivity calculator.

[0032] Specifically, the effective value-added factor k eff Obtained by the following formula:

[0033]

[0034] Furthermore, the intelligent monitoring unit also includes a power level meter and a power distribution meter, wherein the power level meter is suitable for obtaining the power change of the nuclear reactor, and the power distribution meter is suitable for obtaining the power distribution inside the nuclear reactor. Exemplarily, the fast prediction algorithm of the core nuclear thermal artificial intelligence reduced-order model can be used to monitor the power distribution inside the core.

[0035] In this embodiment, the intelligent monitoring unit can also combine artificial intelligence technology to perform fault analysis on the nuclear reactor based on the acquired historical core signals and real-time core signals, and then perform fault targeting, predictive maintenance and decision support on the nuclear reactor 30. By identifying potential fault modes through the intelligent monitoring unit, the startup system 10 can monitor the situation of the nuclear reactor 30 in real time, and timely predict possible fault causes and fault scenarios, which provides a guarantee for solving fault problems, further improves the safety and reliability of the nuclear reactor 30, and ensures the efficient operation of the nuclear reactor 30.

[0036] On the other hand, the starting system 10 further includes a control unit. The intelligent monitoring unit sends a control instruction for controlling the drum to the control unit according to a plurality of core parameters. The control unit controls the rotation angle and rotation speed of the drum according to the control instruction.

[0037] In this embodiment, the control unit can obtain the fault analysis of the intelligent monitoring unit. When the control unit receives the information that the intelligent monitoring unit detects the occurrence of a fault (such as a core power change rate that is too fast, a power level that is too high, etc.), the control unit will automatically take protective measures, such as starting the shutdown protection function (including passive rod drop and passive drum return) to ensure the safety of the nuclear reactor 30. Further, the control unit can automatically adjust and optimize the rotation angle and speed of the control drum under the conditions of the nuclear reactor 30 startup, shutdown and normal operation in combination with the core parameters and the set safety standards, combined with artificial intelligence technology.

[0038] On the other hand, the present application also refers to Figure 2 A nuclear power startup method 20 (hereinafter referred to as "startup method 20") is proposed. Figure 2 A schematic flow chart of a startup method 20 is shown, and the startup method 20 is applicable to the nuclear power startup system proposed in any embodiment of the present application, such as the above-mentioned startup system 10. A flowchart is used in the present application to illustrate the operations performed by the system according to the embodiment of the present application. It should be understood that the previous or following operations are not necessarily performed precisely in sequence. On the contrary, various steps can be processed in reverse order or simultaneously. At the same time, other operations may be added to these processes, or one or more operations may be removed from these processes.

[0039] The nuclear power source startup method 20 comprises the following steps:

[0040] S1: Detecting multiple core signals of a nuclear reactor through multiple external detectors of a measuring unit;

[0041] S2: receiving and analyzing a plurality of core signals detected by the measuring unit through the intelligent monitoring unit, and obtaining a plurality of core parameters of the core according to the core signals;

[0042] S3: Sending a control instruction for controlling the rotating drum to the control unit through the intelligent monitoring unit, and the control unit controls the rotation angle and rotation speed of the rotating drum according to the control instruction.

[0043] Specifically, the startup method 20 can be divided into the following three stages.

[0044] Phase 1: The control unit controls the drum to rotate from the initial position to introduce positive reactivity. In this phase, the nuclear reactor 30 is in a cold zero power, core subcritical state. The control unit controls the drum to rotate from the initial position (in this embodiment, the initial angle is preferably 0° as the initial position) to introduce positive reactivity. The startup method 20 controls the introduction rate of positive reactivity to <50pcm / min. At this time, with the introduction of positive reactivity, the effective value-added factor (k eff ) gradually increases.

[0045] Further, determine the effective value-added factor k eff Is it in the first numerical interval? If the effective value factor k eff When it is in the first numerical interval, it is judged that the core is in a critical state, and the drum is controlled to stop rotating. The first numerical interval is [1-β eff , 1+β eff ], where β eff is the effective fraction of delayed neutrons in the system. This means that in the first stage of startup, the intelligent monitoring unit continuously calculates the effective value-added factor (k eff ), when the calculated effective value-added factor (k eff ) is about 1, the intelligent monitoring unit sends an instruction to stop the rotation of the drum to the control unit. After receiving the instruction, the control unit controls the drum to stop rotating, and then enters the second stage of startup.

[0046] The second stage: In the second stage, the core 31 of the nuclear reactor 30 is in a critical state, but the heat pipes in the reactor are not started. At this time, the thermal power of the nuclear reactor 30 is about 0W, the core temperature is room temperature, and the cooling medium in the heat pipe is still in a solidified state.

[0047] Further, it is determined whether the core is in a critical state for a period longer than a preset time. If the determination result is yes, the drum is controlled to continue rotating. This means that after the core reaches a critical state and stabilizes for a period of time, the effective value-added factor (k eff ) is approximately 1 for a period of time, then the intelligent monitoring unit sends an instruction to rotate the drum to the control unit, and the control unit receives the instruction to control the drum to continue rotating to continuously introduce positive reactivity.

[0048] Then, with the introduction of positive reactivity, the effective multiplication factor (k eff ) gradually increases to exceed the first numerical interval, then the nuclear reactor 30 enters a supercritical state, then the power of the nuclear reactor 30 increases, the substrate is heated, and the temperature of the heat pipe gradually rises to the startup temperature. During the startup of the heat pipe, with the continuous supply of heat, the wall temperature of the heat pipe rises to a certain intermediate value, and then remains almost unchanged for a certain period of time. During this period, a steam interface with a steep temperature drop moves from the evaporation section of the heat pipe to the condensation section (cold zone) of the heat pipe, and the temperature of the heat pipe gradually begins to rise until it reaches a steady-state condition. When the temperature and temperature difference of the heat pipe meet certain conditions (the temperature difference between the evaporation section, adiabatic section, and condensation section of the heat pipe and the normal working temperature of the heat pipe is <50°C, and the temperature difference between the hot end and the cold end of the heat pipe is <50°C), it is considered that the heat pipe has been successfully started. At this time, the core is maintained at a stable power level below 15% FP.

[0049] Furthermore, when the nuclear reactor 30 enters a supercritical state, the fuel temperature inside the core 31 will produce a negative feedback effect, introducing negative reactivity into the core 31, thereby reducing the power of the reactor. At this time, the effective value-added factor (k eff ) will return to the first numerical range, and the nuclear reactor 30 will return to the critical state, thus entering the third stage of startup.

[0050] The third stage: the intelligent monitoring unit continuously calculates the power level of the core and determines whether the power level is greater than or equal to the preset power level. If the judgment result is yes, the drum is controlled to stop rotating. This means that when the control unit receives the drum rotation instruction to control the drum to introduce positive reactivity into the core, the power in the core gradually increases. At the same time, the intelligent monitoring unit continuously monitors the power level and power distribution of the nuclear reactor 30. When the power is increased and stabilized to the preset power level, for example, from the power level of 15% FP to the power level of 100% FP, and stabilized for a period of time, the intelligent monitoring unit sends a command to the control unit to stop the drum from rotating, thereby completing the startup process of the micro mobile nuclear power source.

[0051] The above startup method 20 can control the drum according to the real-time status of the reactor to achieve automatic adjustment and optimization of the startup process, further ensuring the startup safety of the nuclear reactor.

[0052] On the other hand, the present application also refers to Figure 3 A nuclear reactor 30 is proposed, including a core 31 and a shielding layer 37, wherein the core 31 includes a drum 32, a matrix 33, a reflective layer 34, a fuel and heat pipe area 35 and a shutdown rod 36, wherein the fuel and heat pipe area 35 includes fuel and heat pipes, and the heat pipes include an evaporation section, an insulation section and a condensation section.

[0053] The present application detects multiple core signals of a nuclear reactor through a measuring unit, and processes the core signals through an intelligent monitoring unit to obtain an effective value-added factor (k eff ), core parameters, and then the control unit controls the drum according to the core parameters to achieve automatic adjustment and optimization of the start-up process according to the real-time state of the reactor. Furthermore, the present application proposes a nuclear power startup method, which can ensure that the nuclear power startup system automatically adjusts and optimizes the start-up process during the start-up process, thereby further ensuring the start-up safety of the nuclear reactor.

[0054] The basic concepts have been described above. Obviously, for those skilled in the art, the above application disclosure is only an example and does not constitute a limitation of the present application. Although not explicitly stated herein, those skilled in the art may make various modifications, improvements and amendments to the present application. Such modifications, improvements and amendments are suggested in the present application, so such modifications, improvements and amendments still belong to the spirit and scope of the exemplary embodiments of the present application.

[0055] At the same time, the present application uses specific words to describe the embodiments of the present application. For example, "one embodiment", "an embodiment", and / or "some embodiments" refer to a certain feature, structure or characteristic related to at least one embodiment of the present application. Therefore, it should be emphasized and noted that "one embodiment" or "an embodiment" or "an alternative embodiment" mentioned twice or more in different positions in this specification does not necessarily refer to the same embodiment. In addition, some features, structures or characteristics in one or more embodiments of the present application can be appropriately combined.

[0056] Similarly, it should be noted that in order to simplify the description of the disclosure of this application and thus help understand one or more application embodiments, in the above description of the embodiments of this application, multiple features are sometimes merged into one embodiment, figure or description thereof. However, this disclosure method does not mean that the features required by the object of this application are more than the features mentioned in the claims. In fact, the features of the embodiments are less than all the features of the single embodiment disclosed above.

[0057] In some embodiments, numbers describing the number of components and attributes are used. It should be understood that such numbers used in the description of the embodiments are modified by the modifiers "about", "approximately" or "substantially" in some examples. Unless otherwise specified, "about", "approximately" or "substantially" indicate that the numbers are allowed to vary by ±20%. Accordingly, in some embodiments, the numerical parameters used in the specification and claims are approximate values, which may change according to the required features of individual embodiments. In some embodiments, the numerical parameters should take into account the specified significant digits and adopt the general method of retaining digits. Although the numerical domains and parameters used to confirm the breadth of their range in some embodiments of the present application are approximate values, in specific embodiments, the setting of such numerical values ​​is as accurate as possible within the feasible range.

[0058] Although the present application has been described with reference to the current specific embodiments, ordinary technicians in this technical field should recognize that the above embodiments are only used to illustrate the present application, and various equivalent changes or substitutions may be made without departing from the spirit of the present application. Therefore, as long as the changes and modifications to the above embodiments are within the essential spirit of the present application, they will fall within the scope of the claims of the present application.

Claims

1. A nuclear power startup system, suitable for starting a nuclear reactor, wherein the nuclear reactor comprises a core, wherein the core comprises a drum and a matrix, characterized in that: The nuclear power startup system comprises: A measuring unit, the measuring unit comprising a plurality of off-core detectors, the off-core detectors being used to detect a plurality of core signals of the nuclear reactor; an intelligent monitoring unit, wherein the intelligent monitoring unit receives and analyzes the plurality of core signals, and acquires a plurality of core parameters of the core according to the core signals; A control unit, wherein the intelligent monitoring unit sends a control instruction for controlling the drum to the control unit according to the multiple core parameters, and the control unit controls the rotation angle and rotation speed of the drum according to the control instruction.

2. The nuclear power source startup system according to claim 1, characterized in that: The plurality of core parameters include real-time reactivity, power level, power distribution, temperature distribution, core matrix stress distribution and / or core matrix geometric deformation of the nuclear reactor.

3. The nuclear power startup system according to claim 2, characterized in that: The intelligent monitoring unit comprises a digital reactivity calculator, which is suitable for obtaining the real-time reactivity of the core according to the core signal.

4. The nuclear power startup system according to claim 3, characterized in that: The digital reactivity calculator calculates the effective multiplication factor (k eff ) to obtain the real-time reactivity of the core, where the effective multiplication factor (k eff ) is obtained by the following formula:

5. The nuclear power startup system according to claim 2, characterized in that: The intelligent monitoring unit also includes a power level measuring instrument and a power distribution measuring instrument, wherein the power level measuring instrument is suitable for obtaining the power change of the nuclear reactor, and the power distribution measuring instrument is suitable for obtaining the power distribution within the nuclear reactor.

6. The nuclear power startup system according to claim 1, characterized in that: The intelligent monitoring unit performs fault analysis on the nuclear reactor according to historical core signals and real-time core signals.

7. A nuclear power startup method, applicable to the nuclear power startup system as claimed in claims 1 to 6, characterized in that: The nuclear power source startup method comprises the following steps: Detecting a plurality of core signals of the nuclear reactor by means of a plurality of off-core detectors of the measuring unit; Receiving and analyzing a plurality of core signals detected by the measuring unit through the intelligent monitoring unit, and acquiring a plurality of core parameters of the core according to the core signals; The intelligent monitoring unit sends a control instruction for controlling the rotating drum to the control unit, and the control unit controls the rotation angle and the rotation speed of the rotating drum according to the control instruction.

8. The nuclear power source startup method according to claim 7, characterized in that: Sending a control instruction for controlling the rotating drum to the control unit by the intelligent monitoring unit comprises the following steps: The control unit controls the drum to rotate from the initial position to introduce positive reactivity, and the intelligent monitoring unit continuously calculates the effective increment factor (k eff ); Determine the effective value-added factor (k eff ) is within the first value interval, if the effective value-added factor (k eff ) is within the first numerical interval, it is determined that the core is in a critical state, and at this time, the drum is controlled to stop rotating; Determining whether the time during which the core is in the critical state is greater than a preset time, and if the determination result is yes, controlling the drum to continue rotating; The intelligent monitoring unit continuously calculates the power level of the core and determines whether the power level is greater than or equal to a preset power level. If the determination result is yes, the drum is controlled to stop rotating.

9. The nuclear power source startup method according to claim 8, characterized in that: The first numerical interval is [1-β eff , 1+β eff ].

10. A nuclear reactor, characterized in that: The invention comprises a core, wherein the core comprises a drum and a matrix, and the nuclear reactor is suitable for being started by the nuclear power source starting system as claimed in claims 1 to 6.

11. The nuclear reactor according to claim 10, characterized in that The core further comprises a reflector layer, a fuel and heat pipe region and a shutdown rod. The fuel and heat pipe region comprises a heat pipe, and the heat pipe comprises an evaporation section, an insulation section and a condensation section.

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